40-Zr- 94

 40-ZR- 94 JNDC       EVAL-AUG89 JNDC FP NUCLEAR DATA W.G.        
                      DIST-MAR02 REV4-AUG01            20010810   
----JENDL-3.3         MATERIAL 4037                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/        
89-08 Modification for JENDL-3 was made/2/.                       
90-10 mf=5: Spectra at threshold energies were modified.          
93-09 JENDL-3.2.                                                  
      Compiled by T.Nakagawa (ndc/jaeri)                          
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      (3,2), (3,4), (3,16), (3,17), (3,51-91)                     
      (4,16-91)                                                   
      (5,16-91)                                                   
             These data were taken from JENDL fusion file.        
     ***********************************************************  
01-08 Compiled by K.Shibata (jaeri/ndc) for JENDL-3.3.            
     *****   modified parts for JENDL-3.3   ********************  
      (1,451)       Updated.                                      
      (3,1)         Revised.                                      
      (3,2)         Re-calculated.                                
      (3,102)       Revised.                                      
      (3,251)       Deleted.                                      
      (3,203-207)   Calcualted.                                   
      (4,2)         Transformation matrix deleted.                
      (4,16-91)     Deleted.                                      
      (5,16-91)     Deleted.                                      
      (6,16-207)    Taken from JENDL fusion file.                 
      (12,16-107)   Added.                                        
      (14,16-107)   Added.                                        
      (15,16-107)   Added.                                        
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL fusion file /3/  (as of Sep. 1993)                    
            Evaluated and comiled by S. Chiba (ndc/jaeri)         
                                                                  
      Data were taken from JENDL-3.1 except for the following:    
      -  The discrete and continuum inelastic scattering cross    
         sections were calculated with casthy2y and dwucky in     
         sincros-ii system/4/ including contributions from        
         direct reactions.                                        
      -  Angular distributions of discrete inelastics were also   
         calculated with casthy2y and dwucky.                     
      -  The (n,2n) and (n,3n) reaction cross sections (mt=16, 17)
         were replaced with those calculated by egnash2 in the    
         sincros-ii.                                              
      -  Energy distributions of secondary neutrons were replaced 
         by those calculated by egnash2 except for mt=32 which was
         not taken into account in egnash2.  The ddx's of the     
         continuum neutrons were calculated by Kumabe's systema-  
         tics /5/ using f15tob /3/.  The precompound/compound     
         ratio was calculated by the sincros- ii code system.     
      -  Optical-model, level density and other parameters used in
         the sincros-ii calculation are described in ref./4/.     
         Level schemes were determined on the basis of ENSDF/6/.  
     -------------------------------------------------------------
                                                                  
                                                                  
mf = 1  General information                                       
  mt=451 Comments and dictionary                                  
                                                                  
mf = 2  Resonance parameters                                      
  mt=151 Resolved and unresolved resonance parameters             
  Resolved resonance region (MLBW formula) : below 53.5 keV       
    Resonance parameters were taken from JENDL-2.                 
       Parameters were determined on the basis of measured data by
    Boldeman et al./7/  A negative resonance was added to         
    reproduce the capture cross section of 0.0499 barn and the    
    elastic scattering cross section of 6.1 barn at 0.0253 eV/8/. 
    Average radiation widths of 0.090 eV and 0.175 eV were adopted
    to s-wave and p-wave resonances, respectively.                
                                                                  
  Unresolved resonance region : 53.5 keV - 100 keV                
    Unresolved resonance parameters were adopted from JENDL-2.    
    The neutron strength functions, S0, S1 and S2 were calculated 
    with optical model code casthy/9/.  The observed level spacing
    was determined to reproduce the capture cross section         
    calculated with casthy.  The effective scattering radius was  
    obtained from fitting to the calculated total cross section at
    100 keV.                                                      
                                                                  
  Typical values of the parameters at 70 keV:                     
    S0 = 0.370e-4, S1 = 5.500e-4, S2 = 0.360e-4, Sg = 0.534e-4,   
    Gg = 0.190 eV, R  = 6.704 fm.                                 
                                                                  
  calculated 2200-m/s cross sections and res. integrals (barns)   
                     2200 m/s               res. integ.           
      total           6.202                    -                  
      elastic         6.152                    -                  
      capture         0.04981                   0.311             
                                                                  
mf = 3  Neutron cross sections                                    
  Below 100 keV, resonance parameters were given.                 
  Above 100 keV, the spherical optical and statistical model      
  calculation was performed with casthy, by taking account of     
  competing reactions, of which cross sections were calculated    
  with pegasus/10/ standing on a preequilibrium and multi-step    
  evaporation model.  The omp's for neutron given in Table 1 were 
  determined by Iijima and Kawai/11/ to reproduce a systematic    
  trend of the total cross section.  The omp's for charged        
  particles are as follows:                                       
     proton   = Perey/12/                                         
     alpha    = Huizenga and Igo/13/                              
     deuteron = Lohr and Haeberli/14/                             
     helium-3 and triton = Becchetti and Greenlees/15/            
  Parameters for the composite level density formula of Gilbert   
  and Cameron/16/ were evaluated by Iijima et al./17/  More       
  extensive determination and modification were made in the       
  present work.  Table 2 shows the level density parameters used  
  in the present calculation.  Energy dependence of spin cut-off  
  parameter in the energy range below E-joint is due to Gruppelaar
  /18/.                                                           
                                                                  
     For JENDL-3.2, data of inelastic, (n,2n) and (n,3n) reaction 
  cross sections were adopted from JENDL fusion file.  The        
  calculation was made with sincros-ii system/4/ by adopting      
  Walter-Guss omp modified by Yamamuro/4/ for neutrons, Lemos omp 
  modified by Arthur and Young/19/ for alpha, the same omp's as   
  the pegasus calculation for other charged particles and standard
  level density parameters of sincros-ii system.                  
                                                                  
  mt = 1  Total                                                   
    Spherical optical model calculation was adopted.              
    For JENDL-3.3, the cross sections was modified so as to       
    reproduce measured elemental data.                            
                                                                  
  mt = 2  Elastic scattering                                      
    Calculated as (total - sum of partial cross sections).        
                                                                  
  mt = 4, 51 - 91  Inelastic scattering                           
    Taken from JENDL fusion file.  The level scheme was taken from
    ref./6/  Contributions of the direct process was calculated   
    for the levels marked with '*'.                               
                                                                  
           no.      energy(MeV)    spin-parity (direct process)   
           gr.       0.0             0  +                         
            1        0.9187          2  +          *              
            2        1.3002          0  +                         
            3        1.4696          4  +                         
            4        1.6714          2  +                         
            5        2.0576          3  -          *              
            6        2.1513          2  +                         
            7        2.3302          4  +                         
            8        2.3661          2  +                         
            9        2.5077          3  +          *              
           10        2.6045          5  -                         
           11        2.6985          1  +                         
           12        2.8260          2  +                         
           13        2.8463          1  +                         
           14        2.8606          4  +          *              
      Levels above 2.861 MeV were assumed to be overlapping.      
                                                                  
  mt = 16  (n,2n) cross section                                   
  mt = 17  (n,3n) cross section                                   
    Taken from JENDL fusion file.                                 
                                                                  
  mt = 102  Capture                                               
    Spherical optical and statistical model calculation with      
    casthy was adopted.  Direct and semi-direct capture cross     
    sections were estimated according to the procedure of Benzi   
    and Reffo/20/ and normalized to 1 milli-barn at 14 MeV.       
                                                                  
    The gamma-ray strength function (4.89e-05) was adjusted to    
    reproduce the capture cross section of 19 milli-barns at 100  
    keV measured by Musgrove et al./21/                           
                                                                  
    For JENDL-3.3, the cross section was modified so as to        
    reproduce elemental data measured by Stavisskij et al./26/ and
    Poenitz/27/.                                                  
                                                                  
  mt = 22  (n,n'a) cross section                                  
  mt = 28  (n,n'p) cross section                                  
  mt = 32  (n,n'd) cross section                                  
  mt =103  (n,p) cross section                                    
  mt =104  (n,d) cross section                                    
  mt =105  (n,t) cross section                                    
  mt =107  (n,alpha) cross section                                
    These reaction cross sections were calculated with the        
    preequilibrium and multi-step evaporation model code pegasus. 
                                                                  
    The Kalbach's constant k (= 161.8) was estimated by the       
    formula derived from Kikuchi-Kawai's formalism/22/ and level  
    density parameters.                                           
                                                                  
    Finally, the (n,p) and (n,alpha) cross sections were          
    normalized to the following values at 14.5 MeV:               
      (n,p)         10.00  mb (recommended by Forrest/23/)        
      (n,alpha)      4.80  mb (measured by Ikeda+/24/)            
                                                                  
  mt=203   Total proton production                                
    Sum of mt=28 and 103.                                         
                                                                  
  mt=204   Total deuteron production                              
    Sum of mt=32 and 104.                                         
                                                                  
  mt=205   Total triton production                                
    Equal to mt=105.                                              
                                                                  
  mt=207   Total alpha production                                 
    Sum of mt=22 and 107.                                         
                                                                  
mf = 4  Angular distributions of secondary neutrons               
  mt = 2                                                          
    Calculated with casthy/9/.                                    
  mt = 51-64                                                      
    Taken from JENDL fusion file data which was calculated with   
    casthy and dwuck/25/ (dwucky) in the sincros-ii system.       
                                                                  
mf = 6  Energy-angle distributions of secondary particles         
  mt = 16,17,22,28,32,91                                          
    Based on Kumabe's systematics/5/.                             
  mt = 203,204,205,207                                            
    Based on Kalbach's systematics/28/.                           
                                                                  
mf = 12  Photon production multiplicities                         
  mt=16, 17, 22, 28, 91, 103, 107                                 
    Calculated with gnash code /4/.                               
  mt=102                                                          
    Calculated with casthy code /9/.                              
  mt=51-64                                                        
    Transitioin probability arrays                                
                                                                  
mf = 14  Photon angular distributions                             
  mt=16, 17, 22, 28, 51-64, 91, 102, 103, 107                     
    Isotropic.                                                    
                                                                  
mf = 15  Continuous photon energy distributions                   
  mt=16, 17, 22, 28, 91, 103, 107                                 
    Calculated with egnash code /4/.                              
  mt=102                                                          
    Calculated with casthy code /9/.                              
                                                                  
                                                                  
================================================================= 
<> 
================================================================= 
                                                                  
Table 1  Neutron optical potential parameters                     
                                                                  
                depth (MeV)       radius(fm)    diffuseness(fm)   
         ----------------------   ------------  ---------------   
        V  = 46.0-0.25E           r0 = 5.893    a0 = 0.62         
        Ws = 7.0                  rs = 6.393    as = 0.35         
        Vso= 7.0                  rso= 5.893    aso= 0.62         
  The form of surface absorption part is der. Woods-Saxon type.   
                                                                  
Table 2  Level density parameters                                 
                                                                  
 nuclide  syst a(1/MeV)  t(MeV)    c(1/MeV)  Ex(MeV)   pairing    
 ---------------------------------------------------------------  
 38-Sr- 90     9.940e+00 8.530e-01 3.795e-01 6.252e+00 1.960e+00  
 38-Sr- 91     1.090e+01 8.100e-01 1.103e+00 5.625e+00 1.240e+00  
 38-Sr- 92  *  1.288e+01 7.065e-01 2.515e-01 6.391e+00 2.360e+00  
 38-Sr- 93  *  1.386e+01 6.989e-01 1.878e+00 5.664e+00 1.240e+00  
                                                                  
 39-Y - 91     1.050e+01 7.140e-01 8.362e-01 3.521e+00 7.200e-01  
 39-Y - 92     1.012e+01 7.629e-01 2.480e+00 3.191e+00 0.0        
 39-Y - 93     1.150e+01 8.053e-01 1.740e+00 5.854e+00 1.120e+00  
 39-Y - 94     9.149e+00 7.385e-01 1.378e+00 2.222e+00 0.0        
                                                                  
 40-Zr- 92     1.088e+01 8.192e-01 5.122e-01 6.429e+00 1.920e+00  
 40-Zr- 93     1.298e+01 7.000e-01 1.273e+00 5.183e+00 1.200e+00  
 40-Zr- 94     1.275e+01 7.530e-01 4.411e-01 7.019e+00 2.320e+00  
 40-Zr- 95     1.331e+01 6.070e-01 5.453e-01 3.985e+00 1.200e+00  
 ---------------------------------------------------------------  
  syst:  * = ldp's were determined from systematics.              
                                                                  
 Spin cutoff parameters were calculated as 0.146*sqrt(a)*a**(2/3).
 in the casthy calculation. Spin cutoff factors at 0 MeV were     
 assumed to be 5.524 for Zr- 94 and 5.652 for Zr- 95.             
                                                                  
References                                                        
 1) Aoki, T. et al.: Proc. Int. Conf. on Nuclear Data for Basic   
    and Applied Science, Santa Fe., Vol. 2, p.1627 (1985).        
 2) Kawai, M. et al.: J. Nucl. Sci. Technol., 29, 195 (1992).     
 3) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).                
 4) Yamamuro, N.: JAERI-M 90-006 (1990).                          
 5) Kumabe, I. et al.: Nucl. Sci. Eng., 104, 280 (1990).          
 6) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.       
 7) Boldeman, J.W., et al.: Nucl. Phys., A269, 31 (1976).         
 8) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
 9) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).              
10) Iijima, S. et al.: JAERI-M 87-025, p. 337 (1987).             
11) Iijima, S. and Kawai, M.: J. Nucl. Sci. Technol., 20, 77      
    (1983).                                                       
12) Perey, F.G: Phys. Rev. 131, 745 (1963).                       
13) Huizenga, J.R. and Igo, G.: Nucl. Phys. 29, 462 (1962).       
14) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974).    
15) Becchetti, F.D., Jr. and Greenlees, G.W.: Polarization        
    Phenomena in Nuclear Reactions ((Eds) H.H. Barshall and       
    W. Haeberli), p. 682, the University of Wisconsin Press.      
    (1971).                                                       
16) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446      
    (1965).                                                       
17) Iijima, S., et al.: J. Nucl. Sci. Technol. 21, 10 (1984).     
18) Gruppelaar, H.: ECN-13 (1977).                                
19) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980).              
20) Benzi, V. and Reffo, G.: CCDN-NW/10 (1969).                   
21) Musgrove, A.R. de L., et al.: Proc. Int. Conf. on Neutron     
    Physics and Nucl. Data for Reactors, Harwell 1978, 449.       
22) Kikuchi, K. and Kawai, M.: "Nuclear Matter and Nuclear        
    Reactions", North Holland (1968).                             
23) Forrest, R.A.: AERE-R 12419 (1986).                           
24) Ikeda, Y. et al.: JAERI 1312 (1988).                          
25) Kunz, P.D.: Private communication.                            
26) Stavisskij, Ju.Ja. et al.: At. Energija, 15, 323 (1963).      
27) Poenitz, W.P.: ANL-83-4, p.239 (1982).                        
28) Kalbach, C. : Phys. Rev. C37, 2350(1988).